last modified: 27-SEP-1988 | catalog | categories | new | search |

DLC-0031 ZZ-FEWG1, ZZ-GEDT1/4

ZZ DLC-31, 37 Neutron-Group, 21 Gamma-Group Coupled Group Constants Library from ENDF/B

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-FEWG1, ZZ-GEDT1/400,
ZZ-GPDT1/402B, ZZ-NEDT1.401.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
ZZ-GEDT1/400 DLC-0031/02 Tested 01-JUL-1979
ZZ-GPDT1/402B DLC-0031/03 Tested 01-SEP-1979
ZZ-NEDT1/401 DLC-0031/04 Tested 01-JUL-1979
ZZ-FEWG1/H DLC-0031/06 Tested 27-SEP-1988

Machines used:

Package ID Orig. computer Test computer
DLC-0031/02 IBM 360 series IBM 360 series
DLC-0031/03 IBM 360 series IBM 360 series
DLC-0031/04 IBM 360 series
DLC-0031/06 IBM 3033 DEC VAX 11/780
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3. DESCRIPTION OF PROBLEM OR FUNCTION



%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%


FEWG1/H

=======



  FORMAT: ANISN



NUMBER OF GROUPS: 37-neutron, 21-gamma. Energy range 1.0E-11 to 19.64 MeV for neutrons and 0.01 to 14.0 MeV for gamma rays.



NUCLIDES: H, H-3, Li-6, Li-7, Be-9, B-10, B-11, C-12, N, O, F, Na, Mg, Al, Si, P-31, S-32, Cl, Ar, K, Ca, Ti, V, Cr, Mn, Fe, Ni, Cu, Mo, Ba, Gd, Ta-181, W-182, W-183, W-184, W-186,Pb, U-235, U-238, Pu-238, Pu-240.



ORIGIN: DNA Working Cross Section Library and the Evaluated Nuclear Data File (ENDF/B)



WEIGHTING SPECTRUM: 1/E and 300K Maxwellian weighting spectra were used for neutrons.





GEDT1/400

=========



  FORMAT: Gamma-ray  cross section library in SAM-CE format.



NUMBER OF GROUPS: Data are given for the energy range from 1 keV to 100 MeV.



NUCLIDES: Data are included for materials with atomic numbers 1-83, 86, 90, 92, 94, and for some naturally occuring elements.



  ORIGIN: DLC-0007



  WEIGHTING SPECTRUM: --





GPDT1/402B

==========



  FORMAT: Gamma-ray production data in SAM-CE format.



  NUMBER OF GROUPS: --



NUCLIDES: Data are included for H-1, N, O, Al, Si, Ca, Pb, Li-7, B-10, C-12, Mg, Fe, U-235, U-238, Cl, W-182, W-183, W-184, W-186.



  ORIGIN: ENDF/B-IV



  WEIGHTING SPECTRUM:





NEDT1/401

=========



  FORMAT: Nuclear element data in SAM-CE format.



  NUMBER OF GROUPS:



NUCLIDES: Data are included for H-1, H-3, He-4, Li-7, B-10, B-11, C-12, N, O, Na, Mg, Al, Si, Ca, Fe, Cu, Pb, W-182, W-183, W-184, W-186, U-235, U-238, Pu-239, Pu-240.



  ORIGIN: ENDF/B-IV



  WEIGHTING SPECTRUM:



%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%

ZZ-FEWG1: Coupled 37-neutron, 21-gamma group, P3, multigroup library in ANISN format, based on data from the DNA Working Cross Section Library and the Evaluated Nuclear Data File. Cross sections  for the following materials are included: H, H-3, Li-6, Li-7,Be-9,  B-10, B-11, C-12, N, O, F, Na, Mg, Al, Si, P-31, S-32, Cl, Ar, K, Ca, Ti, V, Cr, Mn, Fe, Ni, Cu, Mo, Ba, Gd, Ta-181, W-182, W-183, W-184, W-186, Pb, U-235, U-238, Pu-238, Pu-240. The energy range is  1.0E-11 to 19.64 MeV for neutrons and 0.01 to 14.0 MeV for gamma rays. 1/E and 300K Maxwellian weighting spectra were used for neutrons.

ZZ-GEDT1/400: Gamma-ray cross section library in SAM-CE format. Data are included for materials with atomic numbers 1-83, 86, 90, 92, 94, and for some naturally occuring elements. Data are given for the energy range from 1 keV to 100 MeV.

ZZ-GPDT1/402B: Gamma-ray production data in SAM-CE format. Data are included for H-1, N, O, Al, Si, Ca, Pb, Li-7, B-10, C-12, Mg, Fe, U-235, U-238, Cl, W-182, W-183, W-184, W-186.

ZZ-NEDT1/401: Nuclear element data in SAM-CE format. Data are included for H-1, H-3, He-4, Li-7, B-10, B-11, C-12, N, O, Na, Mg, Al, Si, Ca, Fe, Cu, Pb, W-182, W-183, W-184, W-186, U-235, U-238, Pu-239, Pu-240.
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4. METHOD OF SOLUTION:
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:
DLC-0031/06
The BCD to binary conversion program was run by NEA-DB  against the data library on a VAX-11/780 computer in 3min 15sec.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

The retrieval program BCDEAN converts data from card image format to the binary form required by  SAM-CE.
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9. STATUS
Package ID Status date Status
DLC-0031/02 01-JUL-1979 Tested at NEADB
DLC-0031/03 01-SEP-1979 Tested at NEADB
DLC-0031/04 01-JUL-1979 Tested at NEADB
DLC-0031/06 27-SEP-1988 Tested at NEADB
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10. REFERENCES

- N.M. Greene, et al.,

  "AMPX: A Modular Code System for Generating Coupled Multigroup

  Neutron-Gamma Libraries from ENDF/B",

  ORNL-TM-3706 (March 1976).

- D. Garber, C. Dunford, and S. Pearlstein,

  "Data Formats and Procedures for the Evaluated Nuclear Data File,
  ENDF",

  BNL-NCS-50496 (ENDF 102) Revised Oct. 1975.

- D.E. Bartine, E.M. Oblow, F.R. Mynatt,

  "Radiation-Transport Cross-Section Sensitivity Analysis -

A General Approach Illustrated for a Thermonuclear Source in Air",    Nuc. Sci. Eng. 55, 147 (1974).

- W.W. Engle, Jr.,

  "A User'S Manual for ANISN, A One-Dimensional Discrete Ordinates

  Transport Code with Anisotropic Scattering",

  K-1693, Computing Technology Center (1976).

- J.J. Ritts, M. Solomito, P.N. Stevens,

  "The Calculation of Neutron-Induced Physical Doses in Human

  Tissues",

  ORNL-TM-2991 (1969).

- M.A. Abdou, C.W. Maynard, R.Q. Wright,

  "MACK: A Computer Program to Calculate Neutron Energy Release

Parameters (fluence-to-Kerma Factors) and Multigroup Neutron Reac-    tion Cross Sections From Nuclear Data in ENDF Format",

  ORNL-TM-3994 (July 1973).

- "Protection Against Neutron Radiation",

NCRP-38, National Council on Radiation Protection and Measurements    Washington, D.C. (1971).

- H.C. Claiborne, D.K. Trubey,

  "Dose Rates in a Slab Phantom from Monoenergetic Gamma Rays",

  Nucl. Appl. Tech. 8, 450 (1970).

- W.S. Snyder and C. Neufeld,

  Radiation Res., 6, 1, 67 (1957).

- B.J. Henderson,

  "Conversion of Neutron or Gamma Ray Flux to Absorbed Dose Rate",

  XDC 59-8-179 (August 14, 1959).

- E.A. Straker and M.L. Gritzner,

"Neutron and Secondary Gamma-Ray Transport in Infinite Homogeneous    Air",

  ORNL-TM-4464 (1969).

- J.V. Pace, III, D.E. Bartine, F.R. Mynatt,

"Neutron and Secondary-Gamma-Ray Transport Calculations for 14-MeV    and Fission Neutron Sources in Air-Over-Ground and Air-Over-Sea-

  water Geometries",

  ORNL-TM-4841 (August 1975).

- P.G. Fisher, W.S. Knapp,

  "Aids for the Study of Electromagnetic Blackout",

  70TMP-12, General Electric - TEMP, Santa Barbara, Cal., p. 2.7

  (July 1970).
DLC-0031/02, included references:
- D.E. Bartine et al.:
  DNA Processed Libraries for SAM-CE
  (1976)
DLC-0031/03, included references:
- D.E. Bartine et al.:
  DNA Processed Libraries for SAM-CE
  (1976)
DLC-0031/04, included references:
- D.E. Bartine et al.:
  DNA Processed Libraries for SAM-CE
  (1976)
DLC-0031/06, included references:
- D.E. Bartine, J.R. Knight, J.V. Pace and R.W. Roussin:
  Production and Testing of the DNA Few-Group Coupled Neutron-Gamma
  Cross-Section Library.    ORNL/TM-4840  (March 1977)
- COMAND - AMPX Module to Collapse ANISN Cross Section Libraries.
  Informal Notes
- L.R. Williams:
  LIBGEN - A Special Version of the ANISN Library Generation Routine
  Informal Notes  (1972)
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
DLC-0031/02 FORTRAN-IV
DLC-0031/03 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

D.E. Bartine, J.R. Knight, J.V. Pace, III
and R.Roussin
Neutron Physics Division
Oak Ridge National Laboratory
Oak Ridge, Tennessee, U.S.A.
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16. MATERIAL AVAILABLE
DLC-0031/02
File name File description Records
DLC0031_02.001 INFORMATION 4
DLC0031_02.002 Z RANGE 1-10 1151
DLC0031_02.003 Z RANGE 11-20 801
DLC0031_02.004 Z RANGE 21-30 713
DLC0031_02.005 Z RANGE 31-40 749
DLC0031_02.006 Z RANGE 41-50 767
DLC0031_02.007 Z RANGE 51-60 797
DLC0031_02.008 Z RANGE 61-70 838
DLC0031_02.009 Z RANGE 71-80 1254
DLC0031_02.010 Z RANGE 81,82,83,86,90,92,94 907
DLC0031_02.011 BCDEAN SOURCE 271
DLC0031_02.012 BCDEAN DD CARDS 10
DLC0031_02.013 INPUT 22
DLC0031_02.014 OUTPUT 128
DLC-0031/03
File name File description Records
DLC0031_03.001 INFORMATIONS 4
DLC0031_03.002 SOURCE PROGRAM (F4,EBCDIC) 271
DLC0031_03.003 JCL 10
DLC0031_03.004 SAMPLE OUTPUT 8
DLC0031_03.005 SAMPLE INPUT DATA 2
DLC0031_03.006 LIBRARY (A1-27) 805
DLC0031_03.007 LIBRARY (B-10) 133
DLC0031_03.008 LIBRARY (C-12) 164
DLC0031_03.009 LIBRARY (N-14) 843
DLC0031_03.010 LIBRARY ( MG ) 358
DLC0031_03.011 LIBRARY (U-238) 98
DLC0031_03.012 LIBRARY (O-16) 763
DLC0031_03.013 LIBRARY ( SI ) 2673
DLC0031_03.014 LIBRARY ( CL ) 743
DLC0031_03.015 LIBRARY (W-182) 562
DLC0031_03.016 LIBRARY (W-183) 608
DLC0031_03.017 LIBRARY (W-184) 500
DLC0031_03.018 LIBRARY (W-186) 467
DLC0031_03.019 LIBRARY ( H-1 ) 8
DLC0031_03.020 LIBRARY (PB-NATURAL) 220
DLC0031_03.021 LIBRARY ( CA ) 870
DLC0031_03.022 LIBRARY ( LI-7 ) 26
DLC0031_03.023 LIBRARY ( FE ) 1511
DLC0031_03.024 LIBRARY (U-235) 2060
DLC-0031/04
File name File description Records
DLC0031_04.001 INFORMATION 4
DLC0031_04.002 LIBRARY (NITROGEN) 2377
DLC0031_04.003 LIBRARY (HYDROGEN) 94
DLC0031_04.004 LIBRARY (SILICON) 6811
DLC0031_04.005 LIBRARY (OXYGEN) 3413
DLC0031_04.006 LIBRARY (ALMINUM) 2185
DLC0031_04.007 LIBRARY (LEAD,NATURAL) 2502
DLC0031_04.008 LIBRARY (SODIUM) 3548
DLC0031_04.009 LIBRARY (H-3) 161
DLC0031_04.010 LIBRARY (HE-4) 252
DLC0031_04.011 LIBRARY (C-12) 1526
DLC0031_04.012 LIBRARY (CA) 3081
DLC0031_04.013 LIBRARY (FE) 7121
DLC0031_04.014 LIBRARY (CU) 1169
DLC0031_04.015 LIBRARY (W-182) 1629
DLC0031_04.016 LIBRARY (W-186) 1378
DLC0031_04.017 LIBRARY (U-238) 1195
DLC0031_04.018 LIBRARY (LI-7) 415
DLC0031_04.019 LIBRARY (B-10) 1293
DLC0031_04.020 LIBRARY (B-11) 524
DLC0031_04.021 LIBRARY (MG) 3815
DLC0031_04.022 LIBRARY (K) 1370
DLC0031_04.023 LIBRARY (W-183) 1315
DLC0031_04.024 LIBRARY (W-184) 1261
DLC0031_04.025 LIBRARY (U-235) 2136
DLC0031_04.026 LIBRARY (PU-239) 1384
DLC0031_04.027 LIBRARY (PU-240) 1731
DLC0031_04.028 BCDEAN SOURCE 271
DLC0031_04.029 BCDEAN DD CARDS 10
DLC0031_04.030 BCDEAN DATA 2
DLC0031_04.031 BCDEAN OUTPUT 8
DLC-0031/06
File name File description Records
DLC0031_06.001 INFORMATION FILE 91
DLC0031_06.002 FEWG1-85 CROSS SECTION LIBRARY 17470
DLC0031_06.003 BCBN BCD TO BINARY CONVERSION PROGRAM 45
DLC0031_06.004 ORIGINAL JCL FOR BCD TO BINARY RUN ON IBM 19
DLC0031_06.005 COMMAND PROC.FOR BCD TO BINARY RUN ON VAX 9
DLC0031_06.006 OUTPUT FROM BCD TO BINARY CONVERSION RUN 174
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17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • Z. Data.

Keywords: coupled neutron gamma cross sections, cross sections, data, gamma radiation, group constants, neutron transport theory, photon transport, shielding.